ML17157C449

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Amends 128 & 97 to Licenses NPF-14 & NPF-22,respectively, Revising TS Reporting Frequency of Semiannual Radioactive Release Rept
ML17157C449
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 08/05/1993
From: Boyle M
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17157C450 List:
References
NUDOCS 9309010193
Download: ML17157C449 (37)
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Text

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gO 4**~4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SYLVANIA POWER

& LIGHT COMPANY GHEN C

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0 ACI Y 0 AT NG CENS Amendment No. 128 License No.

NPF-14 1.

The 'Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power Light Company, dated June 1,

1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9309010193 930805~

PDR ADOCK 55000387r P'DBQ

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2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.

NPF-14 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 128 and the Environmental'rotection Plan contained in Appendix B, are hereby incorporated in the license.

PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 5, 1993 Michael L. Boyle, Acting Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

1 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 128 FACILITY OPERATING LICENSE NO.

NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The overleaf pages are provided to maintain document completeness.*

REMOVE X1X XX 3/4 3-81 3/4 3-82 3/4 3-85 3/4 3-86 3/4 12-1 3/4 12-2 3/4 12-13 3/4 12-14 6-19 6-20 6-23 6-24 6-25 6-26 INSERT X1 X*

XX 3/4 3-81 3/4 3-82*

3/4 3-85*

3/4 3-86 3/4 12-1*

3/4 12-2 3/4 12-13 3/4 12-14*

6-19 6-20 6-23*

6-24 6-25 6-26*

ADMINISTRATIVE CONTROLS SECTION PAGE

6. 1 RESPONSIBILITY.......

6-1

6. 2 ORGANIZATION 6.2.1 OFFSITE.......................

6-1 6.2.2 UNIT STAFF...................

6-l

6. 2o 3 NUCLEAR SAFETY ASSESSMENT GROUP FuflCtlOn o

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6-7 6.2.4 SHIFT TECHNICAL ADVISOR................................

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6. 3 UNIT STAFF VALIFICATIONS 6-7 6 ~ 4 TRAININGo ~

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6-7 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATMNS REVIEW COMMITTEE (PORC)

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Ompos1 tlon........................

Alternates......................"...

Meeting Frequency..................

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6-8 6"8 6-8 6"8 R

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6-9 Authorlty..............................................

6-10 ecords.

R 6-10 6.5.2 SUSQUEHANNA REVIEW COMMITTEE (SRC)

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C lternates.............................................

A 6-11 6-11 OnsultantSo

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C 6-11 M t eetlng Frequency.......................--.......

uorum.................................................

Q 6-11 6-11 SUSQUEHANNA - UNIT 1 xix Aeendment No. 29

INDEX ADMINISTRATIVECONTROLS SECTION PAGE SUSQUEHANNA REVIEW COMMITTEE SRC) (Continued)

Review Audits Authority Records

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6 1 1 6-12 6-13 6-13 6.5.3 TECHNICAL REVIEW AND CONTROL Activities Technical Review

.... 6-14 6-14 6.6 REPORTABLE EVENT ACTION

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~ 6 14 6.7 SAFETY LIMITVIOLATION

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6 1 5 6.8 PROCEDURES AND PROGRAMS...... ~..... ~...

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6-15 6.9 REPORTING REQUIREMENTS Routine Reports Startup Reports Annual Reports Monthly Operating Reports Annual Radiological Environmental Operating Annual Radioactive Effluent Release Report Special Reports Core Operating Limits Report 6.10 RECORD RETENTION Report 6-17 6-17 6-17 6-18 6-18 s-~e 6-20 6-20a 6-21 6.11 RADIATIONPROTECTION PROGRAM

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~ 6 22 6.12 HIGH RADIATIONAREA 6-22 6.13 PROCESS CONTROL PROGRAM

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~ 6 24 6.14 OFFSITE DOSE CALCULATIONMANUAL 6-25 6.15 MAJOR CHANGES TO RADIOACTIVEWASTE TREATMENT SYSTEMS.......

6-25 SUSQUEHANNA - UNIT 1 XX Amendment NoA9, LN, 128

INSTRUIVIENTATION RADIOACTIVELIQUIDEFFLUENT IVIONITORINGINSTRUMENTATION LIIVIITINGCONDITION FOR OPERATION 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm/trip setpoints of these channels shall bedetermined in accordance with the methodology and parameters described in the Offsite Dose Calculation Manual (ODCM).

APPLICABILITY:

At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREIVIENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNELCALIBRATIONand CHANNEL FUNCTIONALTEST operations at the frequencies shown in Table 4.3.7.10-1.

SUSQUEHANNA - UNIT 1 3/4 3-81 Amendment No. 7S,

m TABLE 3.3.7.10-1 RADIOACTIVE LI UID EFFLUENT HONITORING INSTRUNENTATION INSTRSKNT 1.

GROSS RADIOACTIVITYNNITORS PROVIDING AUTOHATIC TERHINATION OF RELEASE a.

Liquid Rahraste Effluent Line*

2.

GROSS RADIOACTIVITYNNITORS NOT PROVIDING AUTOHATIC TERHINATION OF RELEASE a.

Service Mater Systea Effluent Line b.

RHR Service Mater Systea Effluent Line 3.

FLIN RATE HEASUREHENT DEVICES a.

Liquid Radwaste Effluent Line b.

Cool ing T~r Slowdown""

HINIHUH CHANNELS OPERABLE 1/loop Aciiou

'ol Iol 102 102 iipklikitiLITYof this nonitor includes the proper functioning of the discharge valve interlocks (saaple puep lut flat, high radiation alara, and radiation aonitor failure).

~~OPERABILITY of this device includes the proper functioning of the Liquid Radwaste Effluent Line

'g discharge valve interlock (i.e. cooling t~r blowdown lcw flee).

1'

TABLE 4.3. 7. 10-1 Continued TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

1.

Instrument indicates measured levels above the alareltrip setpoint.

2.

Circuit failure.

3.

Instrument iadicates a downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

l.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3. 'nstrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards thQ have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall periit calibrating the systeN over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

'CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, per iodic, or batch releases are sade.

SUSQUEHANNA-UNITl 3/4 3-85 Amendment No. 29

INSTRUMENTATION RADIOACTIVEGASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITINGCONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3.7.11-1.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-,1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCEREQUIREMENTS 4,3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATIONand CHANNEL FUNCTIONALTEST operations at the frequencies shown in Table 4.3.7.11-1.

SUSQUEHANNA - UNIT 1 3/4 3-86 Amendment No. 78

3 4.12 RADIOLOGICALENVIRONIVIENTALIVIONITORING 3 4,12 1

IVIONITORINGPROGRAIVI

~

's LIMITINGCONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report per Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a

specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30

days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium', this report shall be submitted if:

concentration(1) concentration(2)

+

p 1 p reporting level(1) reporting level(2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

SUSQUEHANNA - UNIT 1 3/4 12-1 Amendment No. 26

RADIOLOGICALENVIRONMENTALMONITORING LIMITINGCONDITION FOR OPERATION Continued c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3,12,1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d.

The provisions of Specification 3.0.3 are not applicable, SURVEILLANCEREQUIREIVIENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirements of Tables 3.12.1-1, the detection capabilities required by Table 4.12.1-1.

4.12.1.2 Cumulative potential dose contributions for the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 1 3/4 12-2 Amendment No. 9(j), 128

RADIOLOGICALENVIRONMENTALMONITORING 3 4.12.2 LAND USE CENSUS LIIVIITINGCONDITION FOR OPERATION 3.1 2.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m (500 ft') producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a e With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location(s) in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

With a land use census identify a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days.

The sampling location(s),

excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Pursuant to Specification 6.9.1.8, identify the new location(s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCEREQUIREMENTS 4.1 2.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that willprovide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12.1-1 item 4c shall be followed, including analysis of control samples.

SUSQUEHANNA - UNIT 1 3/4 12-13 Amendment No. 7S,>>8

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Comnission.

APPLICABILITY: At al 1 times.

ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Comnission in the Annual Radiological Environmental Operating Report pursuant to Specification 6. 9. 1. 7.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 12. 3 A summary of the results obtained as part of the above required Inter-laboratory Comparison Program shall be included in the Annual Radiological Environmental Operatinggeport pursuant to Specification 6.9.1. 7.

SUSQUEHANNA - UNIT 1 3/4 12-14 Amendlent No.

78

APi,

ADIVIINISTRATIVECONTROLS ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT 6.9.1.8 Routine Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

The period of the first report shall begin with the date of initial criticality.

The Annual Radioactive Effluent Release Report shall include a summary of the

(

quantities of radioactive liquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report to be submitted 90 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction and atmospheric stability, and precipitation (if measured),

or in the form of joint 44 frequency distributions of wind speed, wind direction, atmospheric stability.

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY(Figure 5.1-3) during the report period.

All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the Offsite Dose Calculation Manual (ODCM).

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in file that shall be provided to the NRC upon request.

SUSQUEHANNA - UNIT 1 6-19 Amendment No.79> >28

ADMINISTRATIVECONTROLS ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT+ (Continued)

The Annual Radioactive Effluent Release Report to be submitted 90 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBERS OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR

190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Annual Radioactive Effluent Release Report shall include the following information for each type of solid waste (as defined in 10 CFR PART 61) shipped offsite during the report period:

1.

Container volume, 2.

Total curie quantity (specify whether deteramined by measurement or estimate),

3.

Principal radionuclides (specify whether determined by measurement or estimate),

4.

Source of waste and processing employed (e.g., dewatered spent

resin, compacted dry waste, evaporator bottoms),

5.

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and 6.

Solidification agent or absorbent (e.g., cement; urea formaldehyde).

The Annu'al Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATIONMANUAL(ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office within the time period specified for each report.

SUSQUEHANNA - UNIT 1 6-20 Amendment No. 29, >28

ADMINISTRATIVECONTROLS

6. 12 HIGH RADIATION AREA (Continued)

C.

A health physics qualified individual, i.e., qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the unit Health Physics Supe~vision in the Radiation Work Permit.

6. 12.2 In addition to the requirements of 6. 12. 1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the admini-strati've control of the Shift Foreman on duty and/or the unit Health Physicist.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem" that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the RWP, direct or remote, such as use of closed circuit TV cameras, continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure gF control over the activities within the area.

"Measurement made at 18" from source of radioactivity.

SUSQUEHANNA - UNIT 1 6-23 Amendment No. 2~

ADMINISTRATIVECONTROLS 6.13 PROCESS CONTROL PROGRAM PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1

~

Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.

Documentation of the fact that the change has been reviewed and found acceptable by the PORC.

2.

Shall become effective upon review and acceptance by the PORC.

SUSQUEHANNA - UNIT 1 6-24 Amendment No.g~

~ >28

ADMINISTRATIVECONTROLS 6.14 OFFSITE DOSE CALCULATIONNIANUAL ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

t.

Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.

This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

b.

A determination that the change willnot reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.

Documentation of the fact that the change has been reviewed and found acceptable by the PORC and the Manager-Nuclear Technology.

2.

Shall become effective upon review and acceptance by the Manager-Nuclear Technology.

6.15 MAJOR CHANGES TO RADIOACTIVEWASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste systems, liquid, gaseous and solid:

1.

Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the (PORC).

The discussion of each change shall contain:

a.

A summary of the evaluation tha't led to the determination that the change could be made in accordance with 10 CFR 50.59; b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; SUSQUEHANNA - UNIT 1 6-25 Amendment No. Q7, >>8

ADMINISTRATIVECONTROLS MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SY5TEHS (Continued) e.

h.

An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; An estimate of the exposure to plant operating personnel as a

result of the change; and Documentation of the fact that the change was reviewed and found acceptable by the PORC.

2.

Shall become effective upon review and acceptance by the PORC.

SUSQUEHANNA - UNIT 1 6-26 Aaa~nt No.29

~p,g RECT P

+

O~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SY ANIA POWER Itt LIGH COMPANY EGHEN ELECTRIC COOPERATIVE INC.

DOC ET

0. 50-388 SUS U HANNA ST M

LECTRIC S

TION UNI E

OMENT TO C

ITY 0 ING LIC NS Amendment No. 97 License No. NPF-22 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power 8

Light Company, dated June 1,

1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

~

2

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2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.

NPF-22 is hereby amended to read as follows:

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

97 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PPKL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance: ~Ms~

5 Michael L. Boy

, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATT CHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO.

NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The overleaf pages are provided to maintain document completeness.*

REMOVE Xix XX 3/4 3-82 3/4 3-87 3/4 3-88 3/4 12-1 3/4 12-2 3/4 12-13 3/4 12-14 6-19 6-20 6-23 6-24 INSERT XlX*

XX 3/4 3-82 3/4 3-87 3/4 3-88*

3/4 12-1*

3/4 12-2 3/4 12-13 3/4 12-14*

6-19 6-20 6-23 6-24

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE

6. 1 RESPONSIBILITY 6-1
6. 2 ORGANIZATION
6. 2. 1 OFFS ITE.
6. 2. 2 UNIT STAFF...........,

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6 7 6.2.4 SHIFT TECHNICAL ADVISOR.............

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6. 5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC Function..

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6-8 6-8 6"9 6-10 6-10 6.5.2 SUSQUEHANNA REVIEW COMMITTEE (SRC)

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6-11 6-11 6-11 6"11 SUSQUEHANNA " UNIT 2 Xix

INDEX ADMINISTRATIVECONTROLS SECTION

'USQUEHANNA REVIEW COMMITTEE SRC) (Continued)

PAGE Review Audits Authority Records 6.5.3 TECHNICAL REVIEW AND CONTROL

~... 6-11

. 6-12

~ 6-13 6-1 3 Activities Technical Review

~

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~ 6-14 6-14 6.6 REPORTABLE EVENT ACTION 6-14 6.7 SAFETY LIMITVIOLATION 6-15 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING REQUIREMENTS

~ 6-15 Routine Reports Startup Reports Annual Reports Monthly Operating Reports Annual Radiological Environmental Operating Report Annual Radioactive Effluent Release Report Special Reports Core Operating Limits Report 6.10 RECORD RETENTION 6 6-17 6-17 6-18 6-18 6-19 I

6-20 6-20 6-20b 6;11 RADIATIONPROTECTION PROGRAM 6-22 6.12 HIGH RADIATIONAREA

~.. 6-22 SUSQUEHANNA - UNIT 2 XX Amendment No.g'$,

97

INSTRUMENTATION RADIOACTIVELIQUID EFFLUENT MONITORING'INSTRUIVIENTATION LIIVIITINGCONDITION FOR OPERATION 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm/trip setpoints of

, these channels shall be determined in accordance with the methodology and parameters described in the OFFSITE DOSE CALCULATIONMANUAL(ODCM).

APPLICABILITY:

At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCEREQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNELCALIBRATIONand CHANNEL FUNCTIONALTEST operations at the frequencies shown in Table 4.3.7.10-1.

SUSQUEHANNA - UNIT 2 3/4 3-82 Amendment No. 48~ 97

INSTRUMENTATION RADIOACTIVEGASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITINGCONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3.7,11-1.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCEREQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATIONand CHANNEL FUNCTIONALTEST operations at the frequencies shown in Table 4.3.7.11-1.

SUSQUEHANNA - UNIT 2 3/4 3-87 Amendment No. 43/7

TABLE 3.3.7.11-1 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION INSTRINENT 1.

HAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTEH a.

Hydrogen Honitor 2.

REACTOR BUILDING VENTILATION HONITORING SYSTEH a.

Noble Gas Activity Honitot b.

Iodine Honitor c.

Particulate Honitor d.

Effluent Systea Flow Rate Honitor e.

Saapler Flow Rate Honitor 3.

TURBINE BUILDING VENTILATIONHONITORING SYSTEH a.

Noble Gas Activity Monitor b.

Iodine Honitor c.

Particulate Honitor d.

Effluent System Flow Rate Monitor e.

Sampler Flow Rate Honitor MINIMUM CHANNELS OPERABLE 1/operating train APPLICABILITY

  • A AC7ION 110 112 112 113 113 112 112 113 113

3 4.12 RADIOLOGICALENVIRONMENTALMONITORING 3/4.12.1 IVIONITORINGPROGRAIVI LIMITINGCONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report per Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a

specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30

days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration(1) concentration(2) reporting level(1) reporting level(2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required ifthe measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

SUSQUEHANNA - UNIT 2 3/4 12-1

RADIOLOGICALENVIRONIVIENTALMONITORING LIMITINGCONDITION FOR OPERATION Contiriued ACTION: (Continued) c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12,1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a

revised figure(s) and table for the ODCM reflecting the new location(s).

d.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirements of Tables 3.12.1-1, the detection capabilities required by Table 4.12.1-1.

4.12.1.2 Cumulative potential dose contributions for the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 2 3/4 12-2 Amendment No. P$, 97

RADIOLOGICALENVIRONIVIENTALNIONITORING 3 4.12.2 LAND USE CENSUS LIMITINGCONDITION FOR OPERATION 3.1 2.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m'500 ft~) producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

ar With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification rt.t 1.2.3, identify the new locationlel in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b.

With a land use census identify a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days.

The sampling location(s), excluding the control station

location, having the lowest calculated dose or dose commitment(s)

(via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Pursuant to Specification 6.9.1.8, identify the new location(s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c.

The provisions of Specification 3,0.3 are not applicable.

SURVEILLANCEREQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that willprovide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12.1-1 item 4c shall be followed, including analysis of control samples.

SUSQUEHANNA - UNIT 2 3/4 12-13 Amendment No. N97

RAOIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 3 INTERLABORATORY COMPARISON PROGRAM LIMITIHG CONOITIOH FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a 0 b.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9. 1.7.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.3 A suaeary of the results obtained as part of the above required Inter-laboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9. 1.7.

SUSQUEHANNA - UNIT 2 3/4 12-14 Amendment No.

43 4 ~-

198'

ADIVIINISTRATIVECONTROLS ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT 6.9. 1.8 Routine Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

The period of the first report shall begin with the date of initial criticality.

The Annual Radioactive Effluent Release Report shall include a summary of the

)

quantities of radioactive liquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report to be submitted 90 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction and atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distributions of wind 4 ~

speed, wind direction, atmospheric stability.

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 5.1.3-1a and 5.1.3-1b) during the report period. Allassumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the Offsite Dose Calculation Manual (ODCM) ~

The Annual Radioactive Effluent Release Report to be submitted 90 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBERS OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

SUSQUEHANNA - UNIT 2 6-19 Amendment No. 9"

p ADMINISTRATIVECONTROLS ANNUALRADIOACTIVEEFFLUENT RELEASE RCPORT (Continued)

The Annual Radioactive Effluent Release Reports shall include the following information for each type of solid waste (as defined in 10 CFR PART 61) shipped offsite during the report period:

1. Container volume,
2. Total curie quantity (specify whether determined by measurement or estimate),

3.

Principal radionuclides (specify whether determined by measurement or estimate),

4. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

I

5. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
6. Solidification agent or absorbent (e.g., cement; urea formaldehyde).

The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL(ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office within the time period specified for each report.

CORE OPERATING LIMITS REPORT 6.9.3 The CORE OPERATING LIMITSREPORT, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

6.9.3.1 Core operating limits shall be established prior to the startup of each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

aO b.

C.

d.

e.

The Average Planar Linear Heat Generation Rate (APLHGR) for Specification 3.2.1

~

The Linear Heat Generation Rate for Average Power Range Monitor (APRM)

Setpoints for Specification 3.2.2.

The Minimum Critical Power Ratio (MCPR) for Specification 3.2.3 and 3.4.1.1.2.

The Linear Heat Generation Rate (LHGR) for Specification 3.2.4.

The Thermal Power Restrictions for Specification 3.4.1.1.1 and 3.4.1.1.2.

And shall be documented in the CORE OPERATING LIMITS REPORT.

SUSQUEHANNA - UNIT 2 6-20 Amendment No.~)(~ 97

ADMINISTRATIVECONTROLS HIGH RADIATIONAREA (Continued) within the area and shall perform periodic radiation surveillance at the frequency specified by the unit Health Physics Supervision in the Radiation Work Permit.

6.12.2 In,addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or the unit Health Physicist.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the RWP, direct or remote, such as use of closed circuit TV cameras, continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

a.

Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made, This submittal shall contain:

1.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3.

Documentation of the fact that the change has been reviewed and found acceptable by the PORC.

b.

Shall become effective upon review and acceptance by the PORC.

Measurement made at 18" from source of radioactivity.

SUSQUEHANNA - UNIT 2 6-23 Amendment No.97

E ADMINISTRATIVECONTROLS 6.14 OFFSITE DOSE CALCULATIONIVIANUAL ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated changes to the ODCM:

a.

Shall be submitted to the Commission in the Annual Radioactive Effluent I

Release Report for the period in which the change(s) was made effective.

This submittal shall contain:

/

1.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

2.

A determination that the change willnot reduce the accuracy or reliability of dose calculations or setpoint determinations; and 3.

Documentation of the fact that the change has been reviewed and found acceptable by the PORC and the Manager-Nuclear Technology.

b.

- Shall become effective upon review and acceptance by the Manager-Nuclear Technology.

6.15 MAJOR CHANGES TO RADIOACTIVEWASTE TREATMENT SYSTEMS 6.15.1 Licensee-initiated major changes to the radioactive waste systems, liquid, gaseous and solid:

a.

Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the (PORC),

The discussion of each change shall contain:

1.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; 2.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; 4.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; SUSQUEHANNA - UNIT 2 6-24 Amendment No. gll,97

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